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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217K4731998-04-29029 April 1998 Summary of 980423 Meeting W/Great Bay Power Corp Re Great Bay Power Corp Response to Request for Addl Re Decommissioning Funding Assurance ML20198L2821998-01-0505 January 1998 Summary of 971219 Meeting W/Util in Rockville,Md Re Decommissioning Funding Assurance.List of Attendees Encl ML20202C7341997-11-17017 November 1997 Summary of 971023 Meeting W/Westinghouse in Rockville,Md Re Axial Offset Anomaly (Aoa) & Seabrook Fuel Failures.Copy of non-proprietary Presentation Matl & List of Participants Encl ML20058A1931993-11-18018 November 1993 Summary of 931110 Meeting W/Util in Rockville,Md to Discuss Operational Problems,Plant Performance,Recent Personnel & Organizational Changes,Response to 10CFR2.206 Petition & Actions Re Employee Concerns.Viewgraphs Encl ML20056F8171993-08-0909 August 1993 Summary of Operating Reactors Events Meeting 93-29 on 930804.List of Attendees & Viewgraphs Encl ML20128K8261993-02-0909 February 1993 Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs ML20128C7481993-01-28028 January 1993 Summary of Operating Reactors Events Meeting 93-03 on 930127.List of Attendees & Elements Discussed Encl ML20125E2221992-12-0404 December 1992 Summary of 921123 Meeting W/Util in Rockville,Md Re Transfer of Emergency Planning Responsibility to Commonwealth of Ma. Meeting Agenda,List of Attendees & to FEMA Encl ML20198C6831991-06-26026 June 1991 Summary of 910621 Public Meeting at Science & Nature Ctr, Seabrook,Nh Re Weld Radiographic Concerns ML20058D5281990-10-30030 October 1990 Summary of 901016 Meeting W/Util Re Removal of Limitations Imposed on Use of Odcm.Util Will Submit Formal Request ML20055H3741990-07-20020 July 1990 Summary of 900727 Presentation by Util Re Facility Cycle 2 Fuel Design & Future Fuel Activities.License Amend Will Be Needed for Plant to Go to Higher Enrichment Fuel for 18-month Cycle.Viewgraphs Encl ML20055F8001990-07-12012 July 1990 Summary of 900611 Meeting W/Utils to Discuss Merger Arrangements on Future Operation of Facility ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML20246K5011989-07-0707 July 1989 Summary of Operating Reactors Events Meeting 89-25 on 890705 to Discuss Manual Reactor Trip W/Complications ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 ML20245G6411989-06-15015 June 1989 Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20245A3851989-05-30030 May 1989 Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl ML20247M7961989-05-24024 May 1989 Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20247D3441989-05-16016 May 1989 Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl ML20246L7281989-05-0505 May 1989 Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl ML20246C3261989-05-0404 May 1989 Summary of Operating Reactors Events Meeting 89-18 on 890503 ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML20245F7221989-04-26026 April 1989 Summary of 890420 Meeting W/Util Re Source of Decommissioning Funding & Supplemental Financial Assurance Arrangements to Deal W/Concern of Time Value of Goods & Svcs in Future.Transcript of Meeting Encl ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20245H8011989-02-23023 February 1989 Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl ML20235M1671989-02-17017 February 1989 Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl ML20196B9821988-12-0101 December 1988 Summary of Operating Reactors Events Meeting 88-47 on 881129.List of Attendees,Events Discussed & Significant Elements of Events,Two Events Suggested for long-term Followup & Summary of Reactor Scrams Encl ML20206L9831988-11-25025 November 1988 Summary of Operating Reactors Events Meeting 88-45 on 881115.List of Attendees & Handouts Encl ML20195H0271988-11-25025 November 1988 Summary of Operating Reactor Events Meeting 88-46 on 881122 ML20206E3591988-11-10010 November 1988 Summary of Operating Reactors Events Meeting 88-44 on 881108.List of Meeting Attendees,Significant Events & Summary of Reactor Scrams Encl.One Significant Event Identified for Input to Performance Indicator Program ML20205T4571988-11-0808 November 1988 Summary of 881103 Meeting W/Util in Rockville,Md Re Plant & Applicant Readiness for Low Power Operation.Transcript Encl ML20205H7521988-10-18018 October 1988 Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program ML20207M0771988-10-0505 October 1988 Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl ML20207K9461988-10-0404 October 1988 Summary of 880830 Meeting W/Util in Rockville,Md Re Fire protection-related Issues.Draft Fire Protection Engineering Evaluation, Cables on Svc Bldg Outside Wall & List of Attendees Encl ML20245D8411988-09-28028 September 1988 Summary of Operating Reactors Events Meeting 88-38 on 880927 Re Events Which Occurred Since Last Meeting on 880920 1998-04-29
[Table view] Category:TRIP REPORTS
MONTHYEARML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20154L1661988-05-10010 May 1988 Trip Rept of 880412-15 Mgt Team Visit to Plant Sites,Two Matls Licensees & Region I Ofcs.List of Team Members & Summary of Observations & Perceptions from Visit Encl.Info Deleted ML20196F9951988-02-24024 February 1988 Partially Withheld Trip Rept of 880209-11 Mgt Team Visit to Region V & San Onofre & Trojan Sites Re Integrated Assessment of Mgt Effectiveness Associated W/Regionalized NRR & NMSS Programs ML20012E1591988-02-0808 February 1988 Trip Rept of 880125-29 Site Visit to Participate in Audit of Emergency Preparedness & Public Affairs Div ML20151W0041987-03-12012 March 1987 Submits After Trip Rept ML20213F8661986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl IA-86-778, Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl1986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl ML20206J6561986-06-23023 June 1986 Trip Rept of 860612 Training Session in Lacey,Wa Re Federal Radiological Emergency Response Plans & Meeting W/Utils & State of Wa Concerning Potential Emergency Preparedness Issues.Attendees Listed & Training Agenda Encl ML20244D8391986-05-0707 May 1986 Trip Rept of 860415 Site Visit Re Demonstration for Ultrasonic Exam Procedure of Statically Cast Stainless Steel Primary Loop Welds.Issue of Preservice Ultrasonic Exam of Welds Resolved.Trip Repts by Inel & Bnwl Encl ML20244D8401986-04-22022 April 1986 Trip Rept of 860415 Site Visit Re Demonstration of Ultrasonic Exams Performed on Cast Stainless Steel Primary Piping Welds.Exam Procedure Appears to Meet or Exceed ASME Code Requirements.Written Procedure Not Available ML20154L9181986-03-0606 March 1986 Trip Rept of 851021-24 Site Visits Re Wrong Unit/Wrong Train Events to Determine Whether Simple,Low Cost Improvements Can Be Identified & Implemented ML20237C9681986-02-19019 February 1986 Trip Rept of Attendance at State of Il 860213 Meeting Re Training Session on NRC Incident Response Program & NRC Participation in 860408 Plant Emergency Exercise.List of Attendees & Partial Agenda Encl ML20141H8551986-01-10010 January 1986 Trip Rept of 851112-15 Site Visits Re Wrong Unit/Wrong Train Events.Visit Conducted as Part of short-term Effort to Determine If Low Cost Improvements Can Be Identified & Implemented to Reduce Frequency of Events ML20138A1201985-09-23023 September 1985 Trip Rept of 850617-20 Site Visits Re Reduction of Wrong Unit/Wrong Train Events at Facilities ML20199G3181985-01-15015 January 1985 Trip Rept of 841114-16 Site Visit Re Meetings W/Qa/Qc Inspectors to Emphasize That All Safety Issues Must Be Resolved Before Units Can Be Licensed ML20127B5101984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed IA-85-160, Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed1984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed ML20138M9741983-12-20020 December 1983 Trip Rept of 831129-30 Site Visit Statistical Analysis of Backfit Insp Program ML20205T5371983-02-15015 February 1983 Trip Rept of 830126 Meeting in Bethesda to Discuss Question of Corrective Actions to Be Required of Util Re Finding of Uncertified QC Inspectors at Site ML20134B4611982-09-16016 September 1982 Trip Rept of 820830-31 Visit to Bechtel,Norwalk,Ca to Observe Region IV Insp Concerning Effectiveness of Util/ Bechtel Processing of Field Change Notices for Facility Const.Supporting Documentation Encl ML18139B9671982-07-13013 July 1982 Trip Rept of 820512-14 Visit to Facilities Re Radiological Effluent Tech Specs ML20213D9361981-12-0707 December 1981 Trip Rept of 811005 Visit to Denver,Co & Richland,Wa to Discuss Site Drainage Plans,Meeting W/Westec Consultants on Possible Orographic Effects & Duration of Rainfall & Meeting W/Pnl to Discuss Safety & Environ Review Procedures ML20140G2531976-06-28028 June 1976 Trip Rept of 760614-17 Site Visits Re Relief Valve Test Sequence.Test Results Encl ML20140G2591976-06-15015 June 1976 Trip Rept of 760529 Site Visit Re Witness of Safety/Relief Valve Tests.List of Attendees Encl ML20235C1831975-11-24024 November 1975 Trip Rept of 751111 Visit to Plant Site as Part of Q-1 Review Procedures Re Status of Plant Const.List of Participants Encl ML20235C1511975-10-21021 October 1975 Trip Rept of Site Visit During Wk of 751006 Re NRC Concerns & General Overview by Util of Const Activities.Summary of Site Visit Schedule & Participating Personnel Encl ML20126D8131973-05-0101 May 1973 Trip Rept of 730424-25 Site Visit to Obtain First Hand Knowledge of Site & Environs & to Discuss Possible Problem Areas.Attendance List Encl ML20210B3761972-12-29029 December 1972 Trip Rept of 721218 Site Visit Re Jet Pump Assembly & Torus Ring Header Sys.Dynamic Analysis & Measured Data Not Available.Results & Findings Will Be Described in Rept Scheduled for 730302 ML20210B2621972-10-25025 October 1972 Trip Rept of 721019 Visit to Plant to Investigate Ring Header Problem & Observe GE Blowdown Tests ML20084K2751971-01-27027 January 1971 Trip Rept of 710120 Visit to Plant Re Plans for Replacement of Dome Concrete & Review of Specs for Work.Concrete Removal Operation Satisfactory ML20234E3591964-04-29029 April 1964 Trip Rept of 640318 Visit to Bodega Reactor Site Re Geology of Area. Statement on Bodega Head Power Site Shaft Fault, Encl 1989-08-24
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ATTACHMENT.2 OBaHelle Pacihc Northaest Labora'ories P O Bon 9%
Rg bland. W ashingiur. t. 5 A 99332 Telephone (509, Tele 15 an 375-2838 April 22, 1986 Ted Sullivan Division of Engineering Materials Engineering Branch Office of Nuclear Reactor Regulations Nuclear Regulatory Commission Washington, DC 20555
Subject:
Trip Report on Site Visit to Seabrook Station
Dear Ted:
a On April 15, 1986, a meeting was held with personnel from Seabrook Station, Westinghouse, and the NRC. The purpose of the meeting was to observe and evaluate ultrasonic examinations performed on cast stainless steel primary piping welds.
Before witnessing the ultrasonic. examinations, the examination procedure and data recording were discussed. The discussions produced the following description of the examination procedure and equipment.
j The UT instrument used for examinations was a Sonic Mark I.
the angle beam search unit used for examination was specially designed by Westinghouse and incorporates a water column. ,
l The ultrasonic examination uses a refracted longitudinal j wave during the angle beam examination.
The calibration block used during the UT examinations was block SBRC-5. The block was fabricated from a statically cast elbow found at the Sharon Harris plant. Noise level measurements were made to ensure the calibration block kas representative of the pipe. The noise level measurements were made using two search units in a pitch-catch mode, and ;
compared the noise level of the calibration block to the '
noise level of the pipe.
Thickness measurements of each weldment that was examined were made at 0, 90, 180, and 270 degrees.
g
( W 5Docm w M-
- m. -
j l
Ted Sullivan C8Battelle Page 2 April 22, 1986 .;
l i
During the required section XI zero-degree examination, attenu- )
ation differences between the pipe and calibration block '
were noted.
For each examination, evidence of counterbore and root geometry were documented as proof that the ultrasonic examination penetrated to the required examination volume.
Based on the discussion of the examination procedure and data recording, the examination procedure used at the Seabrook Station appears to meet or exceed ASME Code requirements. However, the actual written procedure used by Westinghouse was not made available for review; therefore, I cannot state positively that the ultrasonic )
examination procedure meets ASME Code requirements.
After discussions about the ultrasonic examination procedure con-cluded, the examination procedure was demonstrated on test blocks provided by Westinghouse and PNL. A description of both sets of test blocks is contained in NUREG/CR-3753. The demonstration of the examination procedure showed the following:
Using the examination procedure, an inservice inspection technician was able to detect mechanical fatigue cracks in both Westinghouse sampler.
- When used on the PNL test samples, the procedure and technician l.
could detect thermal fatigue cracks when the examination was I conducted from the columnar side. The examination procedure and technician could not unambiguously detect thermal fatigue cracks when the examination was conducted on the equiaxed grain side.
Based on the demonstrations performed on both the Westinghouse and PNL samples, I conclude that the examination procedure will perform better when used for examination of a columnar grain struc- )
ture. !
Prior to the site visit, NRC personnel requested inspections of l two welds. The selds were 5-1-1 and 5-1-2 (Loop 2 steam generator nozzle-to-elbow and elbow-to-nozzle) . The results of the examina-tions witnessed showed:
- Evidence of the weld root and weld counterbore could be de-tected during the zero-degree and angle-beam examinations, but not continuously on all pipe.
L-__--__-- -
Ted Sullivan C*Battelle Page 3 April 22, 1986 During the angle examination of weld #5-1-2, signals attributed to weld counterbore were not continuous but intermittent.
Representatives from Seabrook Station stated that during construction, portions of the weld counterbore accessible from the stcam generator manway were blended via hand grinding.
A blended counterbore might not be detected during an angle-beam examination and could create the intermittent signals witnessed during the examination.
The ambient acoustic noise level shown on the ultrasonic instrument ranged between 20-30% full screen height.
Based on the demonstrations and discussions at Seabrook station, I conclude:
- 1. The demonstrations show that adequate penetration of the cast piping material could be obtained during both zero-degree and angle-beam examinations.
- 2. Intermittent signals detected during angle-beam examination and clarified as geometry should be well documented so that subsequent inservice examinations may verify that the extent of the geometric indication has not changed. Any changes in the geometric signals detected during' subsequent inservice inspections should be carefully evaluated to determine the cause of the change.
- 3. All ultrasonic examinations had not been completed at the time of the site visit. If an examination of any weld does not provide reasonable assurance of penetration, a request for relief should be processed for that weld.
If you have any questions or I may be of further service, please contact me at 509-375-2838.
Sincerely, 3 I T. T. aylor I NDE&M Section TTT:kw cc: Boyd Brown, EG&G Idaho I
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